ML20092G829
| ML20092G829 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 06/20/1984 |
| From: | Kemper J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| OL, NUDOCS 8406250254 | |
| Download: ML20092G829 (21) | |
Text
r s
PHILADELPHIA ELECTRIC COMPANY 23O1 M ARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 JUN 201984 (2151841 4502 JOHN S. KEMPER V IC E -PR E SID E N T Ehts8hE E RING AND RE SE ARCH Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Limerick Generating Station Design Verification Program, Unit 1
References:
1)
A. Schwencer to J. S. Kemper letter, dated May 15, 1984 2)
J. S. Kemper to A. Schwencer letter, dated May 6, 1984 File:
GOVT l-1 (NRC)
Dear Mr. Schwencer:
The reference 1) letter requested additional information concerning the design experience of Torrey Pines Technology reviewers. Enclosed are 15 copies of completed experience forms for each of the reviewers.
The summary, also enclosed, reflects the Task assignments for each reviewer.
Sincerely, See Attached Service List g,
GJB/pd 17/2 9
W A ffh 0
A
7 I
cc: Judge Lawrence Brenner (w/o enclosure)
Judge Richard F. Cole (w/o enclosure)
Troy B. Conner, Jr., Esq.
(w/o enclosure)
Ann P. Hodgdon, Esq.
(w/o enclosure)
Mr. Frank R. Pa mno (w/o enclosure)
Mr. Robert L. Anthony (w/o enclosure)
Charles W. Elliot, Esq.
(w/o enclosure)
Zori G. Ferkin, Esq.
(w/o enclosure)
Mr. Thanas Gerusky (u/o enclosure)
Director, Penna. Emergency (w/o enclosure)
Management Agency Angus R. Iove, Esq.
(w/o enclosure)
David Wersan, Esq.
(w/o enclosure)
Robert J. Sugannan, Esq.
(w/o enclosure)
Spence W. Perry, Esq.
(w/o enclosure)
Jay M. Gutierrez, Esq.
(w/o enclosure)
Atanic Safety & Licensing (w/o enclosure)
Appeal Board Atanic Safety & Licensing (w/o enclosure)
Board Panel Docket & Service Section (w/o enclosure)
Martha W. Bush, Esq.
(w/o enclosure)
Mr. James Wiggins (w/o enclosure)
Mr. Tinothy R. S. Campbell (w/o enclosure)
Ms. Phyllis Zitzer (u/o enclosure)
Judge Peter A. Morris (w/o enclosure)
y1 g
/
EXPERIENCE
SUMMARY
N-.
Project Management Years Experience (Design) Average F. D. Carpenter 33 PFR Committee - Task E 27.8 S. L. Koutz 28 F. O. Hall 29 T. R. Colandrea 25 A. M. Harris 25 R. G. Wunderlich 32 Tasks A & B 12.8 S. Bresnick i
18 W. P. Malay 28 R. B. Patten 1
K. J. Baylor 12 Tasks C & D 17.
(Design-15.)
A. A.' Schwartz 22 11 J. D. Stanley 35 35 W.'R. Arnold 15 15
.L. E. Penzes 15 15 E. P. Gagnon 15 15 C. F. Dahms 5
3 F. T. Lin 16 16 P. K. Patel 13 13
- "'~"
^
PROJECT 2524 LIMERICK INDEPENDENT DESIGN REVIEW TECHNICAL REVIEWERS - NUCLEAR PLANT DESIGN EXPERIENCE EMPLOYMENT!
DATES l
EMPLOYER.
l ACTIVITIES' l
l Feb 1957 to lCA Technologies Inc l Research, development,. design, arid manufacture in nuclear materials technology present l San Diego, CA l for HTCR reactors (Peach Bottom, Ft. St. Vrain). Design and construction of l (27+ years) l inpile experimerits for the TRIGA, MTR, ETR, CETR test reactors including l
l testing and operation phases.
Development and implementation of QA programs l associated with nuclear power NSS suppliers. Project and Program management l
l of independent desf gn verification and quality systems evaluation for major l
l safety systems in nuclear power plants. Directed nuclear materials management, l
l health physics programs, nuclear hot cell facility, nuclear waste processing l
l facilities, and licensing activities.for SNM handling and reactor operations.
1951to1957lU.S.NavyElec-lMaterialsengineeringtechnologyassociatedwiththedevelopment, design, and
.tronics laboratory l manufacture of navy electronic systems and hardware.
U.S. hbfa$'kir Sta-l Chemical, metallurgical, and physical gesting of materials for tion (1 yr.)
l U.S. Naval Station.
s l
l l
l l
l l
l l
l l
l.
l e
l l
l l
l l
l l
l l
l l
l
'3TALEkPERIENCE YEAR (S) 33 MONTH (S) a SIGNATURE MNd%D DATE 5/31/84
/
, mp -__
s
. PROJECT.2524
- _<
- R: viewer S. L. Koutz 1~
- g C
.[
A
~
. LIMERICK INDEPENDENT, DESIGN REVIEW TECHNICAL REVIEWERS NUCLEAR PLANT DESIGN EXPERIENCE c.
L i
MPLOYMEf!T l
'"l DATES-l EMPLOYER ACTIVITIES ~
{
7 5
8 g
,a 1.-
1956 to l GA
~lHTdRdesign,'LWRdesignreviews 2/ ~
J, p
present l San Diego, CA l
- o Ghie'f Engineer reporting to Vice President on engineering and technical issues l
~
^*
/
l sr l
l joChairmanof.)PotentialFindingsCommittee.forall,IDVPsonLWRs
~,
l l
lo Director. Plant Engineering Division responsible.for design and development of gas-1 l
l l
cooled reactor systems (HTGR & GCFR)-
.l l
l
~
lo Director - New Concepts Division for work on gas turbine cycle-power plants, l
process-heat and heat dissipation systems, and fusion power plants j
l lo Techitical Director of Asia-Pacific Division of General Atomic International.
l l
~l l
lo. General Manager of Gas-Cool Reactor Division for 300 MW(e) power plant design, start-
~
l l-~up of-Peach. Bottom #1 and Fort St. Vrain gas-cooled reactors
-l l
'lo Nanager of -the design and installation of the first TRIGA test reactor and a prime l
[ contributor in the nuclear and engineering analysis of the TRIGA reactor series.
l l
l l
I g
8
'l l
l l
l l
l l
l l
l
.B I
l l
l l
l l
l fT$LEXPERIENCEYEAR (S) 28 MONTH (S)
SIGNATURE JSIMM DATE 6/1/84 c)
.a.
~
6 4
Oa e
s 3
w.
.I w
q q
q s
s e
N M
kk h
k h. %, %
.N 4
s e?.
e4 m
N 4
=
m s
e
=
a 1
's e
m-50 0
.5 t
.k-E 5
==
s gN.
E UH C
k Es W
9 m-
)
\\w$ bs 4 -
2 an t
d E
55 I
s S8 N
k y
H E U
il b%.
n i
1A {k 3,. h 4
h bh
=
m-s.
u
=
5 e
3
'N e
5
%i m 4%
e r
g sg b
-Q SO s
Os E
53 u3 1
s
- h 14 d
h Y}
/
N p,
~?
o
'I.
L3 h
e i
u 3
x u
i k
k' )
a L
)
h x
,n x
y u.
Nn
_o h
E
.T
~1.
..i..,
Q S
,gy LQ { ~'- % -.
g i
==
=
Te
[N s
m-zu b ;-
m s
M S*
C'
% }
. 3,N) N s
.h k
w*
M OM b,
,s ms a
g a.
i ay y
a an
(.
s s
.,. I m
55 3
e Q.
9s wu E
.\\ o y
g um z
M6 4 Q m :m
'e
/
N
.c
),
m Ws d-s m
d X
.l k9' 4 G. Q h
"E f
M
~
a E
e s
d3 W
s%
b
<w
$i 6b S ik o
5 E
8 ws 4
E 2
bY h,
4 W
0 4
6 m a<
0 m
____________________________________________________________________________E!
W d
o
+
.~
wa p
'1,_'. $
L E
3 bd 5
EQ e
i i
go y v m:
u s.
se _ _ n _ _
xw e
PROJECT 2524 LIMERICK INDEPENDENT DESIGN REVIEW TECHNICAL REVIEWERS - NUCLEAR PLANT DESIGN EXPERIENCE PLOYMENT l l
DATES l
EMPLOYER l
ACTIVITIES l
!GeneralAtomic,SD Head of Engineering A'nalysis. Peach Bottom IITGR Project
.1 1959 l
l 1960 l
l Section Chief Reactor Design.
In charge'of Peach Bottom reactor vessel, control and' emergency r
'l l rod and fuel handling equipment design and development l
l 1982 l
l Associate Manager - Reactor Plant Engineering.
In charge of NSS plant preliminary design l-l (excluding core), including prototype component development (ESADA and RG&E Brookwood Proj.)
l l
'h 1965 l
l Associate Manager - Reactor p} ant engineering for Fort St. Vrain Project.
In charge of NSS l
l preliminary design (excluding core), including prototype component development. Participated l
l in PCRV development and plant licensing.
1967 l
l Associate Division Manager - Large llTC$. Participated in conceptual and preliminary designs l
l for large steam-cycle HTGR power plants and for a possible helium direct-cycle gas turbine j
l HTGR power plant.
i e
8
.1 1970 l Senior Technical Advisor - HTGR Engineering.
Involved in analysis of Fort St, Vrain startup l
l problems and rectification. Pursued technical liaisoiwith GA's German licensee. Became l
l familiar with pebble bed reactors including TilTR. Also involved in review and development j
j of Large llTGRs for Delmarva, Philadelphia Electric, etc.
1 1975 l
l Dcpartment Manager - Preliminary Design. Responsible for design studies of an alternate j
j large steam cycle HTGR power plant, contributing to component design, and for direct cycle j HTGR and steam-cycle CCFR plant studies.
5 i
. 1980 i
. Senior Technical Advisor - HTGR Engineering.
lCATechnologiesInclDesignReviewBoardmemberandprincipalreviewerforsystemsengineeringof.2240MWand Ent
l l
l l
l l
l l
l l
i
,)
,LEXPERIENCE YEAR (S) 1 MONTH (S)
I SIGNATURE bMkl1[k DATE 5[l/9@
"Y '
l l t
" ^ ' " * ' "
PROJECT 2524 LIMERICK INDEPENDENT DESIGN REVIEW TECHNICAL REVIEWERS - NUCLEAR PLANT DESIGN EXPERIENCE 1
hPLOYMENTl DATES l
~ EMPLOYER l
ACTIVITIES' 0Cf5' 7 lH.O.Cmar11Ga g g,c4 y m a n jV,9yry tvcicr e79st c o i77,77 e n c i,9 c a p-p lMic wnuicee,l>J! l Powc ra. pu+ur c.ompoWeurs c.e w e m usass e 5 p--{g
-l l frunen <s ene tnicer, PRa' 7'/R ' 2*c=*S.
l l
$/c, y G R T & cem oc.o qi c5~uc;isu$2run quo e2/Grueen.iug meivacsirnew <-
j
' f.
l l foosi nca.r es$cci&& wmY parsi'cM, r=n/3izicah'oM besay7 l l gy crR5arrep 6 r=
/t'7GR-PL eWr Gorspew'sk7s l
lx.e.
PCR V, t-tuees, M=~T'trec. eseries., S;2m<77 geucmenta S.
l l
l l
l l
l l
l l
l l
l l
l l
l l
l l
l l
l l
l l
l l
l l
l l
l l
l l
l l
l SIGNATURE M 8 / I m M.t /Ij /
DATE S /pr[r /
& EXPERIENCE YEAR (S) 3 Z.
MONTH (S)
i A.
\\
s a
x q
{$
9L I
c _)
M4 5
m 2h v
c E
ww d
p f b E
b5 C
i N
S p
m zw b,
Y. Q h
m er s
N 84 Z U
L%
n 5
8
-.la 4
w" a
86
~
a o.
ma n
SS Y
ex c/
e c),
a}
4 ss
+
6
-w
..b E3
\\ i3 i
D.
J am
. j; j
M
=
N M
e-C C
m e-u%
&
- e ;--
a 5
m m
H A
CO e
-~.
M 3
T.
IL) w a
t
>=
)
g m
w m
a z
W w
j~
E.L
.o D
W D
U
_____________________._______________________________________________________ g t:
+
x M
t3 m w
m O<
N W
gO A,
e
_J r
w sS H
LJ o
cr -
PROJECT 2524
' LIMERICK INDEPENDENT DESIGN REVIEW TECHNICAL REVIEWERS - NUCLEAR PLANT DESIGN EXPERIENCE PLOYMENT!
CATES EMPLOYER
!NuclearPokerPlant:
ACTIVITIES'
'52-5/54 !WestinghouseElec. !Fluidsystemsdesign' engineer-firstnuclearpower'edsubmarineanditsprototype.
Responsibl for preparation;P&lD, systems description, sizing pumps, valves; preparation equipment speci-l Corp, Bettis Lab.,
e l Pittsburgh, Pa.
I fications 3
8
)/55-ll/57l Bettis Laboratory. l Same as above for next generation of submarines. Also served one year as project engineer l
l interfacing with testing operations on the prototype plant.
l l
L/57-12/65l W' house - Resident l Represented NSSS on (1) resolution and disposition shipbuilder identified problem / deficiencies l Mechanical Engr at l of equipment.(2) check-out and testing. of;installdd equipment and systems for new construction l Mare Is. Naval Shipt modification, overhaul, and refueling.
l ya d, Vallej o, Ca. l r
l l
(66-10/66 lW' house - Submarinef Prepared repair and modification procedures for components and fluid systems
-l Air Craft Carrier l associated with the primary plant.
jNuclear Prototype l
l Site, Idaho Falls j
1/66-12/72l General Atomic Co. l Quality Engineer - Assigned the Quality responsibilities for components control rod drives.
l San Diego, Ca.
l steam generators, various ASME nuclear class pressure vessels,. piping, valves.
l l
/73-12/75 l l Branch Mgr., Procurement and Quality Engineering - responsible for assuring quality j requirements were specified in design documents, drawings, specifications, and the j preparation of inspection plans, and the review of supplier documentation.
l l Branch Manager, Quality Compliance - responsible for inspection of equipment at suppliers j plant, surveys and evaluations of suppliers.
Performed audits for
/76-12/79 {Sotthern Cal Edison l Site QA Engineer at commercial nuclear operating power plant.
l Co., San Onofre.
l compliance to Station Orders, Station Operating Procedures, Technical Specifications, jSan Clemente, Ca.
[ and regulatory requirements. Performed surveillance on repair, modification, and refueling l
l activities.
f30-12/82lGeneralAtomic lPerformedinternalauditsofalldivisions.
l l
l l
l l
AL' EXPERIENCE YEAR (S) 28 MONTH (S)
SIGNATURE bd ' 9. b O af DATE @5IB4 i
l d
w,
- g i
C Q
C (y) 4 9
w B
4sL J
e#
a b
- e 0
N Q
f Fp 4 k
c a
1 7
- h
/
a o<
Y og2 j
5 ?
N E-e 6" M 14 3
e
.c o.
g S
$kD T
y
< aC
'd 2 z
O l
34 a5 e
t l
29 C 1 k*K y0 k
Q C E 2o 4 e
i l
3 w
s o
w a
o e
4 42 L
w w j *m o
g x
'1,
d*
4 F--
2 4
E u e g w.
g
>z m
u v
we w
s4
- es m
yb q
in 1
a cr: -
w g,
z0 3 4, 3 d *s Ud M
3' e
e.
e ao s
o ok N
~
~
0
?
I l N NN U
UU
. 0 *c g 3V t
3 s r e os g
x o
b,]
M' A5k o
L<
'n '
v 'n m
> P
'b h-we t
,"1 L >0 7<
o C
o o<
o 2
4 x
g 4 g
m zw w
Yb 6*p
$12 E,.6 a
k d <h 6 br
$b d
ez 0
t
.o w w3 g
wo I
6$
N
'u u$g.
um tt g3 oyt
- h$-
2
<2 e b H5 a
s er 3
is a
2 w
Ed k
b k
,g 3
o 5 w
-3 $
~
k $k 3$
z a
%s e a e $-
aa x
5 k
M s
21 z
o 5
=
e g2 k_
i e
W
'M x
w IandM$
3
%g 2 o
t *
^
f fN e g e! z wn' w
a s
w ef a% b
<2m as e
n o$$
Gddic o@n c
S e
w 0
reas w
..............................__..............a.........._............_....g b
M d
A E
[3 m k
xw w
R<
R
- w o
a
>= F-=
X o<
W i
$O tt g
.2 6
A __ _ ______
3-5
Reviewer K. J. B;ylcr PROJECT 2524 Engin ;r B.S. in Phy:ics-LIMERICK INDEPENDENT DESIGN REVIEW-Penn State univ.
TECHNICAL REVIEWERS - NUCLEAR PLANT DESIGN EXPERIENCE LOYMENT l l
DATES l
' EMPLOYER l
ACTIVITIES' l
l I
L-84 l CA Technologies.Incl o Quality Assurance Reviews of:
San Onofre 2 (Seismic Review) l San Diego, CA l
Palo Verde 1, 2, 3 (Design Control) l l
Waterford 3 (Design Control) l l
Marble Hill 1, 2 (Construction Review) l l
l l o Equipment Qualification Analyses for Susquehanna 1, 2 l
l l
l o Nuclear Analysis and Shielding Calculations for Generic Studies and for j
j Peach Bottom Control Rods in the FSV-1 Shipping Cask l
l l
l o Stress Analysis (Thermal) in HTGR Fuel Blocks I
I Dec1980'CATechnologiesInclOnloantoBechtelPowerCorp.,Norwalk,CAtoperformnuclearanalysisandshieldingworkfo l
- San Diego, CA l o Vogtle 1, 2 3
3 loMaanshan1,2
~
{
loKuosheng1,2 loKorea5,6
. lGA Technologies,Inc! o Analysis and determination of nuclear performance characteristics of gas-cooled fast i f}0 lSanDiego,CA l
breeder reactor.
Calculations of breeding ratio, mass flows, blanket shuffling effects, recriticality of slumped cores, power distribution, effect pf s' team entry on criticality,,
e i
l sensitivity of performance to fuel types using diffusion theory, transport theory and auxiliary codes.
Reporting in detail on the methods and calculational results.
i4-57
- lConvair,
! o Prel.imi. nary studies of radiation effects on humans, materials, components, and l San Diego, CA l
systems for proposed nuclear-powered airplane.
l l
52-54 lGE - Knolls Atomic ! o Analysis of radiation effects on properties of metal cladding, elastomeric seals, l Power Lab, I
etc., for nuclear submarine "Seawolf."
l lSchenectady, N.Y.
l
- l l
l l
l EXPERIENCE YEAR (S) 12 MONTH (S)
SIGNATURE '$d//mMOMb/82 ' DATE 06/01/84 L
n A_
PROJECT 2524 LIMERICK INDEPENDENT DESIGN REVIEW TECHNICAL REVIEWERS - NUCLEAR PLANT DESIGN EXPERIENCE i
LOYMENT l l
DATES l
EMPLOYER l
ACTIVITIES-l l
72 -
!CA, San Diego, CA ! Engineering task leader for Independent Review and Physical Verification of res nt l
l Waterford SES Unit 3 Emergency Feedwater System l
l l
l Coordinated technical review of Palo Verde Units 1, 2, and 3.
l l Also served as lead engineer for structural review.
l l
l l Identified review features for seismic review of San Onofre Units 2 and 3; l
l and performed technical review of structures and components.
l l
l l Performed piping analysis for LWR plants.
l l
l Responsible engineer for filter related modifications to Rancho Seco plant.
l l
l l Responsible engineer for liners, penetrations, closures, and cooling water l
l systems in PCRV for HTCR plants.
l l
l l Lead engineer for development and testing of a circumferential prestressing l
l system for PCRVs.
I l
l l
l l
l l
l l
l l
l l
l l
l l
l l
l l
l l
l l
l A
s l//
/s
/
s L EXPE IENCE YEAR (S) // /22.- MONTH (S) 7[4[
SIGNATUR [M(((([ 'Yd DATE k/Mk fRr! ' 70pf>L
/
//
V
.T N
4
'b R,.
s s
W y
s 1
1 t
.I a
+q V
K u
o
.\\e s
s a
s, d b^
h h
IN)
)
k.
x)
I y.D N'
m s
4~
f is k' 'd
%s!
.,Y e s)C - !
F 1
h t
s x; 4
t
~
t N.
N
{
j v
r i
g' t
- D (
\\
e i
[
'N d
9 dS
't:-
h t
N X ~b i 5
%.+g 3,
t s
N-N i
x4 H.
~
,i i
e e
s 4
@d
) Q 'l
' $ E l 's 'k 8
m 55 E
N
- t t ' 5 ? d }5' 3'
?
.g 5
'4 ze 0
g m
s A
!S E:
Pi
! N4}'sL.ss 4*
Q
=
en t;
we 3e s.
os
%g l
u 4
x s t = j'
.?
!d m"
s w
me s
s v'+
!4 4
- ! i c $ 4 0 s
S8
't e
2-
%e e s.
w.e t.
s e
s c
s s
-s "4
UW uE E E, Y ' "U 't 4 s k'N N b 1
1 4
x._
t C
4-u m
at v
g k,y s'S 't' j n
i w
x
=
4 s
4 ys c
v g
g' l
g N s +'
u
0-------------------------
m
)s f
io v.
6 4
5 k
3 G
S t
1 I-I, w
.s y
!5 4
we a
d
=
we
+
r S
x b
O I
4 s
a m
A _____ _________ _ _ - _
K-
s%T e
,5
{k
~
t
-x{
M s
8
~
x s
g 3
?
U k{
L U{
3 E
a E d it 4
Ie*3 a
2 a
13 2
%4 s 5 e t 3 3.i
)
l'a te u
eM tEq a
2
.l 4$3 \\
t
%g s
=
N R CR y
0 ia 9
se 47 o
?
w 4
k k ):
E3 D
h es b 4
e aI ie i
0 NQ g "w-
,R A
4E B
4 5
kk k
g,Rs%4).8 q
- ER
~
E to J
0 3.t 2
.o 4 +E r e
=
q a
a V IQ E'
sw o
e w
"h h{'
f?Q b,h 58 sd3 30 4 Mk 4
e qSgQ j kt t Of L:; r p
e {4 k
)'u O q$$
E g{
s.
a-%
$R Og g
hw q
b H
sm s
sg w g 4^ 2 R P e *i s
6 4 1
i
" %" yen E
@s 8
)
h l *4 @a 3' EE k
d
.1 @ 8 (
' m' g
n s
R l
s as s%
}
%v EW R
Hu WW CT o
m NUEf@3))}3N a
s s s s
.3 h
4
$N513$$dd$
k 5
W D
u s
'it aw e
a3 a
a m
@Y g
{
t
<W O
@c g G.S '*
% n n
M n k, R R. RAARRR R
E r t, n
s m
s s
t r
g i
~
) {s,..
N
.g A M
x s
4 I
t e
u y
s W
X Ih d'
D v
A y
u hA g
7 4
o
.w u
Y 5
A Q
9
)
C 4
i d3 o
)
~
'23',T11. y p
y i
Is 2
s 1
4
- s. sg y
s m
a m
s I
W o
o w
A
\\
h "Q
l d
?"
3
~ D2 u
y j}'
MA h
5 33 m
=s e
+
s 2
--n
=m t-
.e 4 m
g sa 3 dg
.I F.a { w @P,%
M Oh b
3
-s
.o S
m" y-v i
OE N
I j
o hh
(
B" 5
4, f Yt s 7 a>
N al I) i sm 1
gg Ba 6l) e n
m E
+
s;:
m s
a
%= a +[
l'd s( kA E
u z
+w 5=
(5 g q
_c gwm y o
m
'q
,a
.s
$ F t
s 3.
-)
a y
n a
u 4x 6 w"
- 5. 4 3 D 9
fb 14 G
du d
5
_______9.________.______________________________________________________g m
n
~
b n.
w c~
x
>- r W
on o
y
\\
a X
+
1 B
.?
y
}-
1
- 'kr{.s
\\ er nz t
- s 2
s 4;
,4
=
s
+
-9g+.gau q-(6 e
n x
V
.z e
f I
k' N
},3
. ] -
,k
{
f~'
=
m t
m
'N, e
N d R
t-4
,)a g
e j
gi 4
4 ld4 1
4 d{
'{
g si si(j ti-
<x t
1
(\\ N k
.~
=
m b
bM b
s os si B"
g( 4y
,."'(x a
se EEj g
t i
d(*
4p, 87 v
~
e a
u k,
gy Ct:
o q'
D N*
e a
s1 a
3 A
i D
w l
l
____________________.;_______________________________________________________M
- m l
50 E
0.c
+
w N
N A
p Keviewet*
C tlA14 ttA 5 LIMERICK INDEPENDENT DESIGN REVIEW TECHNICAL REVIEWERS - NUCLEAR PLANT DESIGN EXPERIENCE
)LOYMENT l l
DATES EMPLOYER ACTIVITIES ~
Nuclear Experience:
>-9/79 l GA Technologies,Incl In Structural Engr. Dept., assisted in stress analysis of GCFR core support structure.
1-9/80 lSanDiego, Cal.
In Structural Engr. Dept., performed stress analysis on graphite post / seat for core l
l support structure of an HTGR.
~I l
.-10/81 l
l In General Engineering Dept, performed. inelastic stress analysis of HTGR reheater tubing l
l experiencing cyclic loading at high temperature.
s.
e 11-12/81 ;
l In Gen. Engr. Dept., performed electric equipment walkdown at a BWR, and assisted in l
equipment qualification program.
8 Il-3/82 l
l In Gen Engr. Dept., performe'd seismic design review of a PWR and assisted in l
l writing procedure for review program.
!-8/82 l
lInMaterialsEngr.&TestingDept., performed fossil fired power plant research
' l l
s l-9/82 l
lInGen. Engr. Dept.,performedmechanicalequipmentandpipingwalkdownataPWR.
- -7/d3 l
lInMat. Engr. & Testing Dept.', performed magnetic load analysis and stress analysis l
l for a fusion reactor first-wall / blanket structure.
l-8/83 l
lInGen. Engr. Dept., performed structural walkdown at a PWR and assisted in selection of items to be reviewed in walkdown.
s L-present !
! In Mat. Engr. & Testing Dept., performed fracture analysis of HTCR superheater and superheater and reheater tubing. Also performed thermal stress and fracture analysis of a fission reactor first-wall.
l l
l l
l l
l l
l l
l l
l l
l L E'XPTRIENCE YEAR (S)
Fi MONTH (S) 7 SIGNATURE [ a M [x k M I DATE 6 / &'/
L
PROJECT 2524 LIMERICK INDEPENDENT DESIGN REVIEW TECHNICAL REVIEWERS - NUCLEAR PLANT DESIGN EXPERItNCE
@YMENT l l
ATES EMPLOYER l
ACTIVITIES-tv-G8 GA Technologies Inc.I Acted as a project eriginee'r for construction, surcrvision and inspection to l
of TRIGA !! ARK II Reactor shield structure at Savar Bangladesh for ecent l
l Bangladesh Atcmic Energy Ccenission._
s l
l Participated in the independent construction review of Parble Hill Nuclear l
l Generating Station Units 1 and 2 for Public Service Indiana.
Acted as l.
team leadar of civil structural insp2ction group and walked cbun for verification of reinformd concrete structures, steel structurcs and cable l
l tray supports of selected rafety-related systcas.
Prepared walkcbwn l
l prccedures and final walkdowr, ccports.
l Perfomed the d2 sign reviews of condensate storage pool, steam generator l
-l suoport and sliding base and cable raceway supports for Louisianm Power &
l l
Licht, Waterford Steam Electric Station Unit 3. Also reviewed the on-site l
construction d2 sign at the field.
l l
Participated in New York Long Island, Shoreham Nuclear Paeer Plant I
construction independent verification program.
Acted as a teaa leader of I
l pipe suptort verification walkdown and inspected 29,000 pipe supports.
l l, Prepared walkdown procedures and final walkdown report.
l l'
l l
Performed a scirmic design review of safety injection systs connecting to I
reactor coolant nozzle 1A for San Onofre Nuclear Pcwer Units 2 and 3.
l l
l l
Perfonned stress analysis of Class 1 piping safety injection lines for l
l San Onofre Nuclear Generating Station and Palo Verde Nuclear Generating l
l Station.
O I
l l
Perfonned seismic analysis and prepared ~ a Design Report of underground l
l prestressing concrete pipes for nuclear servi cooling water systen, l
Korea Nuclear Units 5 and 6.
l l
Author of design reports (equivalent to FDAR and ESPR) on structural j
design of containment building and fuel building, Korea Nuclear Units 5 L
and 6.
EXfERIENCE YEAR (S) 15 MONTH (S)
II' SIGNATURE -@h/m,p// M,'
DATE 7Ndv3/, #ff o
fu'
- j j
KevleWer F.
K. rAtel PROJECT 2524
=
LIMERICK INDEPENDENT DESIGN REVIEW TECHNICAL REVIEWERS - NUCLEAR PLANT DESIGN EXPERIENCE YMENT l l
TES l
' EMPLOYER l
ACTIVITIES ~
-6/72 ' Foster Wheeler CorpI Design and stress analyses of an intermediate heat exchanger which transports heat energy I from a primary sodium to the secondary sodium loop. The equipment was designed per ASME I
! Code criteria for the FFTF.
(Associated with this task from 6/70 to 6/72) l l
-6/74 l Culf United Fuel ~,d Performed design and stress analyses on a two mechanical components, namely, Dump Heat l Corp.
l Exchanger (sodium to air) and cold trap for the FFTF.
Both components were analysed
! based on the ASME Code criteria for elevated temperature operation (1331-5) 8
' f 1) Conceptual design and analyses of the various components including PCRV, reactor
- 8/81 General Atomic l
l containment, heat exchanger, thermal barrier, etc., for a direct cycle HTGR. Analysis l
l were performed using either hand calculations or finite element programs.
l l
l l 2) Work as consultant to Bechtel's Los Angeles Power Division.
Carried out Class 1 and l
l Class 2 piping analyses on the different projects including ANPP units 1, 2, 63, l
l San Onofre Units 2 & 3, Korea Units 5 & 6.
I g6/83 lCygna Energy l 1) Piping support design and analyses for Diablo Canyon Unit 1
!*##1C'"
!2)EquipmentqualificationofmechanicalequipmentforWashingtonPowerWNP2 l
l 3) Block wall design and analysis for Boston Edison l
l I
bpresenpCA Technologies Incj l
i e
l l
i l
l l
l l
l l
-l l
e A*f
. A /7 A
,/
i
@XPERIENCE YEAR (S)
/3 MONTH (S)
SIGNATURE Nd DATE YM//
r
"/
_ _ _ _ _ _ _ _ _ _. _ _. _. _ _ _ _